Text

Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl
	ML20199E388
Person / Time
Site:	Catawba
Issue date:	12/23/1998
From:	Peebles T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Gordon Peterson; DUKE POWER CO.
References
	NUDOCS 9901200412
	Download: ML20199E388 (102)
	v • d • e

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( December 23, 1998 L ,

Duke Energy Corporation !

ATTN: Mr. G. R. Peterson, Site Vice !

President, Catawba Site -

l 4800 Concord Road

' York, SC 29745-9635

SUBJECT:

MEETING

SUMMARY

- TRAINING MANAGERS' CONFERENCE CONDUCTED l ON NOVEMBER 5,1998 - CATAWBA NUCLEAR STATION j

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Dear Mr. Peterson:

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This letter refers to the Training Managers' Conference conducted at the Richard B. Russell '

Building on November 5,1998. Representatives from all utilities in Region Il participated in the meeting.

Enclosure 1 was the agenda used for the Training Managers' Conference, and Enclosure 2 is the list of attendees. We appreciate the participation of you and your staff and believe that the .

goal of providing an open forum for discussion of operator licensing issues was met. Mr. Gallo, Chief of the Operator Licensing and Human Factors Branch, Office of Nuclear Reactor i Regulation (NRR), made a presentation as noted in the slides in Enclosure 3.

Additionally, I am enclosing our preliminary schedule for FY 1999 and FY2000 as Enclosure 4.

l Please review the schedule and supply comments to my staff or myself.

If you have any questions regarding the content of this letter, please contact me at (404) !

562-4638.

Sincerely, Original signed by l Thomas A. Peebles l Thomas A. Peebles, Chief Operator Licensing and Human 200088 eerformance Branen Division of Reactor Safety Docket Nos.: 50-413 and 50-414

. License Nos.: NPF-35 and NPF-52 '

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Enclosures:

As noted - I l

cc w/encls: i W. H. Miller, Training Manager, Catawba Nuclear Station M. S. Kitlan, Compliance G A. Copp, Licensing 9901200412 981223 PDR ADOCK 05000413 p 1 815

h ca)

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DEC 2 Distribution w/encis: l PUBLIC B. Michael, DRS 1

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BMICHAEL: T EBLES 12/ f /98 12// f /98 l Doc Name:

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Revised November 3,1998 TRAINING AND OPERATIONS MANAGERS' COlWERENCE U.S. Nuclear Regulatory Commission, Region II Atlanta, Georgia Meeting Agenda November 5,1998 Richard B. Russell Building Auditorium Thursday.11/5/98 8:00 a.m. Conference Registration 8:20 a.m. Introduction Thomas A. Peebles, Chief, Operator Licensing & Human Performance Branch '

8:30 a.m. Opening Remarks William Travers, .

Executive Director of Operations 8:50 a.m. Welcome / Issues Raised the Last Meeting Bruce S. Mallett, Director Division of Reactor Safety 9:15 a.m. break 9:45 a.m. Other Issues Robert M. Gallo, Chief Operator Licensing Branch, NRR 10:15 a.m. lessons Learned from Recent Exams Charlie Payne Sampling exam criteria 11:00 a.m. Examination Communications Ron Aiello Exam Development & Coordination 11:30 a.m. Lunch

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- 1:00 p.m. Written Examination Questio0s and Answers Rick Baldwin / George Hopper 2:30 p.m. JPM Examples of questions Rick Baldwin / George Hopper 3:30 p.m. Open Session - Other Issues Training Managers 4:00 p.m. Meet with Principle examiners All 4:30 p.m. Adjorn

License Applicant Administre1i,ve )Valkthrough Examination--NRC-1 ,

Examiner Sheet t

l A.1FShift Staffing t Question 1: A lic'ensed RO has been off shin for 6 months to assist in outage scheduling. He is informed that he is needed to join a shin crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has l maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shins in the control room as the OATC during the past month under the direction of a shin RO.

What additional requirements must be met by the RO before he may fill in for the vacationing RO?

References Allowed? YES1NO I

i Answer: The RO must complete an additional 24 (40 - 16) hours of"under direction" on- '

shift time that must include a plant tour and shift turnover.

Reference:

SSP-12.1, Conduct of Operations, p. 61 and 62 l K/A 2.1.4 (2.3/3.4) l I

Applicant Response: SAT UNSAT l

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. . . _ . . . _ . . _ . - . . . _ . . ._ _ . _.. - _ _ _ ... _ _ . _ _ .... . _ _ .. _ _ m 4.

r L ATTENDEES AT THE NRC REGION 11 TRAINING MANAGERS CONFERENCE NOVEMBER 5,1998 '

/ Sid Crouch ~ ATTSi David Lane- - Sonalysts, Inc.

Bill Fitzpatrick INPO< )

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! CP&L j L ~ Rick Gamer HR Supv Ops Tmg

' William Noll BK Ops Tmg Supv -

Max Herrell ' BK lTmg Mgr ,

Scott Poteet - RB Exam Team Leader I Ralph Mullis BK Ops Mgr

, Tony Pearson BK Ops Tmg

' Anthony Williams RB Tmg Mgr Crystal River - FPC

Wes Young CR Supv OpsTng i Tom Taylor - CR Dir Nuc Ops Tmg

l. Ivan Wilson CR Ops Mgr b Ken McCall CR Mgr Ops Tmg'

- Duke Power Gabriel Washbum OC Req Team Leader Ronnie B. White, Jr MG Tmg Mgr

- W. H. " Soap" Miller ' CT Site Tmg Mgr i Paul Stovall OC Mgr Oper Tmg ,

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Bentley Jones OC Tmg Mgr j L

James'Teofilak .

CT- .. Ops Tmg Mgr' l Alan Orton MG ~ Ops Tmg Mgr Richard Bugert Corp . Ops Tmg Spec l

E!%L Maria Lacal TP Tmg Mgr i Dennis L. Fadden _SL Services Mgr - -

[

. Jo Magennis Corp . Tmg Assessment Spec L-Tom Bolander SL Exam Development i

. Steve McGarry . TP Maint Tmg Supv Southem Nuclear (SNC)

' John C. Lewis HT Tmg & EP Mgr

l. Bill Oldfield _FA Nuc Ops Tm Supv i: Steve Grantham HT, Ops Tmg Supv 1 Scott Fulmer - FA Mgr Tmg & EP

-Joel Deavers ' FA Sr Pit Inst

Bob Brown. VG_ Tmg Mgr Dan Scukanec .VG Ops Tmg Supv -

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4 Virainia Power Steve Crawford NA Sr Inst Nuc 4 Harold McCallum. SR Supv Ops Tmg -'

- TVA Dick Driscoll SQ Tmg Mgr Walt Hunt SO Ops Trng Mgr Denny Campbell BF SRO Ops Inst Jack Cox WB Trng Mgr

- John Roden WB Ops Trng Mgr Tom Wallace WB Ops Supt

- V. C. Summer- SCE&G Al Koon SM Ops Trng Supv

' NRC Particioants Tom Peebles R 11 Operator Lic. Br. Ch.

Rick Baldwin R 11 ~ Sr. Examiner George Hopper R 11 Sr. Examiner Ron Aiello R 11 Sr. Examiner Charlie Payne R 11 Sr. Examiner William Travers NRC Executive Dir. Ops.

R. M. Gallo NRR Br. Ch. OL Bruce Mallett R 11 Div. Dir. Reactor Safety A

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. l FY 99 INITIAL EXAM SCHEDULE AND RESULTS l

l December 14,1998 RO SROl SRO U TOTAL Date Plant Chief Pass # Pass # Pass # Pass #

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9/28/98 Sequoyah GTH 4 4 4 4 10/5/98 Harris RFA 2 2 5 5 7 7 11/30/98 Oconee GTH 2 2 5 5 7 7 11/30/98 St Lucie & RSB 6 3 9 12/14/98 1/25/99 McGuire & DCP 6 3 2 11 2/8/99 l 2/8/99 C. River & GTH 6 6 12 2/22/99 2/8/99 B. Ferry MEE 4 1 5 3/29/99 Surry & RSB 5 2 4 11 4/12/99 4/12/99 Watts Bar & MEE 6 3 5 14 4/26/99 5/10/99 Farley GTH 7 1 8 5/24/99 Catawba & PMS 8 5 3 16 6/7/99.

6/28/99 St. Lucie RSB 1 4 5 07/26/99 Robinson MEE 3 2 2 7 08/30/99 Turkey Pt & RFA 20 20 9/13/99 136 4 4 5 5 9 9 18 18 RESULTS TO DATE 100 100 100 100 No initial exams scheduled for: Brunswick, North Anna and Vogtle FY 00 region 11 write part of Summer & Hatch

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l FY 00 INITIAL EXAM SCHEDULE AND RESULTS December 14,1998 RO SRO-l SRO-U TOTAL Dr.te Plant Chief Pass # Pass # Pass # Pass 0 9/27/99 Summer GTH 6 6 l region ll write ,

10/18/99 Hatch DCP 10 2 12 region II write 12/13/99 Vogtle RSB 3 5 2 10 .

1 2/14/00 Brunswick & DCP 12 3 15 -

2/28/00 03/"/00 Oconee 7 10 1

704/10/00 Harris <maybe 1o/oo) -10 705/03/00 St. Lucie GTH 6 5 11 l 1

705/**/00 B. Ferry 6 3 3 12 705/03/00 McGuire 4 8 12 706/07/00Farley RSB 10 2 12 707/26/00 Crystal River .RFA 3 3 3 9 r;gion ll write?

708/**/00 Sequoyah 4 2 2 8 709/04/00 Surry? 10 709/11/00 North Anna 12 0 0 42 0 46 0 27 0 149 P7' d:signates tentative No initial exams scheduled for; Catawba Robinson Turkey Point l Watts Bar i

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i i-l Operator Licensing I

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Region 11 -

Training Managers' Conference November 5,1998 Robert M. Gallo, Chief Operator-Licensing and Human Performance Branch 6

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OPERATOR LICENSING l lSSUES i

l j o Part 55 Rulemakings L -

Status

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Schedule l; o Final Revision 8 of NUREG-1021 i

i i-j o Examination Quality and Results i ~

[ o Generic Fundamentals Exam

!; o Requal Inspections i IP-710.01) 4 i

o Recent Information Notices j -

Exam Integrity ilN 98-15?

l Sampling Plans ilN 98-28?

Eligibility ilN 98-37?

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RECENT LESSONS LEARNED .

by Charlie Payne Southeastern Training Manager's Conference i

~ November 5,1998 t

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I POLICY CLARIFICATIONS ,

i e in general, the NRC prefers.that the written exam be administered after the operating tests are complete.

i Allows more time to finalize test.

Vlore flexibility if delays occur.

Less stressful on candidates.

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PQ_LICY CLARIFICATIONS l; i

e in general, license class sizes of greater than .

B candidates will be scheduled for 2 weeks as follows: ;

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1 St exam week ,

off-week for documentation of week 1 ,

performance 2"d exam week 3

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PC'LICY CLARIFICATIONS O Examination submittals - 2 copies of draft and final exams (written, JPMs, and simulator scenarios). El5ctronic copy is also desired.

O Written exams submittals will be reviewed by following a sampling process. When criteria

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are met, review will be stopped and licensee 4

called.

Criteria - 10 unacceptable questions out of 30 questions sampled ,

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i RECENT LESSONS LEARNED 1 >

SRO-only Questions intended to sample those K/As specific to

, SRO duties (above and beyond those needed by an RO}.

purpose is to meet the requirements of 10 CFR 55.43(b) (items (1) - (7)?.

i K/A catalog cross-references K/As to associated portions of 10 CFR 55.

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2.0 GENERIC KNOWLEDGES AND i ABILITIES 2.1 Conduct of Operations l 2.1.1' Knowledge of conduct of operations requirements.

(CFR: 41.10 /45.13)

IMPORTANCE RO 3.7 SRO 3.8 >

l 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

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(CFR: 41.10 / 45.13) -

IMPORTANCE R O 3.0 SRO 4.0 2.1.3 Knowledge of shift turnover practices.

1 (CFR: 41.10 /45.13) i IMPORTANCE RO 3.0 SRO 3.4 2.1.4 Knowledge of shift staffing requirements.

M (CFR: 41.10 / 43.2)

IMPORTANCE RO 2.3 SRO 3.4 2.1.5. Ability to locate and use procedures and directives related to shift staffing and activities.

(CFR: 41.10 / 43.5 /45.12)-

IMPORTANCE - RO 2.3 SRO 3.4 2.1.6 Ability to' supervise and assume a management role during plant transients and

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= upset conditions.

t (CFR: 43.5 / 45.12 / 45.13)

IMPORTANCE R O 2.1 SRO 4.3 2.1.7 Ability to evaluate plant performance and make operationaljudgments based on operating characteristics / reactor behavior / and instrument interpretation.

! (CFR: 43.5 /45.12 / 45.13) l IMPORTANCE R O 3.7 SRO 4.4 2.1'.8 Ability to coordinate personnel activities outside the control room.

l -.-+- -(CFR: 45.5 / 45.12 / 45.13)

IMPORTANCE- RO 3.8 SRO 3.6.

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2-1 NUREG-1123, Rev. 2 {

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2.1 Conduct of Operations (continued) l l

2.1.19 Ability to use plant computer to obtain and evaluate parametric information on i system or component status.

(CFR: 45.12)

IMPORTANCE RO 3.0 SRO 3.0 i

2.1.20 Ability to execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 4.3 SRO 4.2 -

2.1.21 Ability to obtain and verify controlled procedure copy.

(CFR: 45.10 / 45.13)

IMPORTANCE RO 3.1 SRO 3.2 2.1.22 Ability to determine Mode of Operation.

l O -(CFR: 43.5 / 45.13)

IMPORTANCE R O 2.8 SRO 3.3 2.1.23 Ability to perform specific system and integrated plant procedures during

different modes of plant operation.

(CFR: 45.2 / 45.6)

IMPORTANCE R O 3.9 SRO 4.0 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 45.12 / 45.13)

IMPORTANCE RO 2.8 SRO 3.1 2.1.25 Ability to obtain and interpret station reference materials such as graphs /

monographs / and tables which contain performance data.

(CFR: 41.10 / 43.5 / 45.12)

IMPORTANCE RO 2.8 SRO 3.1 2.1.26 Knowledge of non-nuclear safety procedures (e.g. rotating equipment / electrical /

high temperature / high pressure / caustic / chlorine / oxygen and hydrogen).

(CFR: 41.10 / 45.12)

IMPORTANCE RO 2.2. SRO 2.6 fa 2

2-3 NUREG-1123 Rev. 2 l i

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i 2.4 Emergency Procedures / Plan (Continued) 2.4.32 Knowledge of operator response to loss of all annunciators.

(CFR: 41.10 / 43.5 / 45.13)

IMPORTANCE RO 3.3 SRO 3.5 2.4.33 Knowledge of the process used track inoperable alarms.

_ (CFR: 41.10 / 43.5 / 45.13) l .IMPORTANCE RO 2.4 SRO 2.8 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including sydem geography and system implications.

L (CFR: 43.5 /45.13)

IMPORTANCE RO 3.8 SRO 3.6 1 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.

(CFR: 43.5 /45.13)

IMPORTANCE RO 3.3 SRO 3.5 l 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations. l (CFR: 43.5)

IMPORTANCE R O 2.0 SRO 2.8 2.4.37 Knowledge of the lines of authority during an emergency.

(CFR: 45.13)

IMPORTANCE - R O 2.0 SRO 3.5 1

2.4.38 Ability to take actions called for in the facility emergency plan / including (if required) supporting or acting as emergency coordinator. '

(CFR: 43.5 / 45.11)

IMPORTANCE RO 2.2 SRO 4.0 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.

(CFR: 45.11)

IMPORTANCE R O 3.3 SRO 3.1 2.4.40 Knowledge of the SRO's respor.sibilities in emergency plan implementation.

(CFR: 45.1.1)

IMPORTANCE RO 2.3 SRO 4.0 2.4.41 Knowledge of the emergency action level thresholds and classifications.

r (CFR: 43.5 / 45.11)

IMPORTANCE RO 2.3 SRO 4.1 NUREG-1123, Rev 2 2-14 l i

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RE_C_ENT LE_SSC'NS LEARNED SRO-only Questions (Cont'd}

c. SRO-only questions will be based on following categories: A.2, G2.1, G2.2, G2.3, -

and G2.4.

differences between SRO and RO outlines .

shifts only 11 K/As from Tier 2 to Tiers 1 & 3.

~ Other 14 flexible.

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ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: Date of Exam: Exam Level:

K/A Category Points Tier Group '

Point X K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 1 1

%!L Ein Ws' M

~% 26 Emergency &

1 m m 51;m,22p M,' va , Q~EfW.in

=

g 7 , ,.y ,

Abnormal P1 ant 2

ggW ks $g g[ g 17 g g.. ap w sm Tier :;p gp gj Evolutions pp #gj 43 +7 Totals E Fw'd W.

um &m G' n Mm 4 ,

J'l 1 23 2.

2 13 P1 ant Systems 3 4 Tier 40 fl Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 + 't Note: Attempt to distribute topics among all K/A categories; select at least one topic from every K/A category within each tier.

Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

Systems / evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the category / tier.

NUREG-1021 10 of 39 Interim Rev. 8, January 1997

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ES-401 BWR R0 Examination Outline Form ES-401-2 Facility: Date of Exam: Exam Level:

K/A Category Points Tier Group Point K K K K K K A A A A G

- Total 1 2 3 4 5 6 1 2 3 4 3-Emergency &

I m w, g

% h k 13 g p Abnormal 4 awe iiid Gs W& 19 Plant 3 h ( $! $ jy 4 Tier E$ @ ;i$$ j 36 Totals @%% (&{ $g?

1 28 2.

Plant 19 Systems 3 4 Tier 51 Totals

3. Generic Knowledge and Cat I Cat 2 Cat 3 Cat 4 Abilities 13 Note: -

Attempt to distribute topics among all K/A categories; select at least one topic ' rom every K/A category within each tier.

Actual point totals acrt match those specified in the table.

Select topics from many systems; ovoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

Systems / evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the category / tier.

NUREG-1021 16 of 39 Interim Rev. 8, January 1997

RE_C_ENT LESSC'NS LEARNED :

Sampling Critena i i

intent.of prodess is to avoid exam predictability.

also to avoid excessive use of repeat test items.

first use systematic process to develop sample plan using topics from K/A catalog, then use acility question resources to accomplish the plan. .

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RED _ENT LE_S_ SONS LEARNED ~

Samplinc Criteria (Cont'd) each topic in each tier & group should be sam aled at least once unless insufficient c uestions exist to do this. If a I topics have been samalec once and other questions neec to be selected, the arocess should be systematic and unbiased.

final sample plan should have a fairly even balance across all Ks & As.

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RE_C_ENT LESSONS LEARNED -

Sampling Criteria (Cont'd}

up to 25 questions from last two NRC exams, facility licensee exams, tests & quizzes (except final audit test) may be used.

t C7ief Examiner (CE) has the option to unilaterally shift or change the selected K/As.

up to 5 site-specific priorities may be identified with CE concurrence (K/A valtw may be < 2.5 with sufficient justification). ]

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OTHnR .

Record Keeping per 10 CFR 55 are required to provide '

evidence that the applicant has successfully completed the facility licensee's requirements to be licensed as an operator. ,

this includes successful manipulation of the controls of their facility. As a minimum,5 significant control manipulations which affect '

reactivity or power level.

10

e OTHER -

Record Keeping (Cont'd) this informatipn should be retained and avai able for ins aection from time of license application to license expiration. .

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OTHER -

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Requal Control Manipulations if have program based on SAT process, list in i 10 CFR 55.59(cX3) does not need to be strictly followed. !

should have something similar based on alant JTA and specific plant priorities.

some manipulations are individual operator oriented, most would be team oriented.

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s I C>THER i Requal Control Manipulations (Cont'd) credit for accomplishment should only be given for active participation in the manipulation.

NOTE: control manipulations are not i synonymous with reactivity manipulations.

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4 Examination Communications 1 1

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1 Examination Development I

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i j Coordination i

1 By i

i l Ronald F. Aiello

Facility Suggested improvements

1. The exam development team and lead examiner slou c meet at the beginning of the deve opment arocess to estab ish common grounds for the development anc execution of the examination:

Changes and interaretations to the NUREG.

Scoae of the exam ceveloament and administration process.

Lessons learned from the last exam administerec.

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! 2. Move due dates for t 7e outline and the I exam back to 90 anc 60 days prior to prep i wee <. This will provide more time for l dxamination review ay tie examiner (s).

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j 3. SSNTA continue with efforts to j standardize document formats for j examination tools (JPMs and scenarios).

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l 4. Examiners maintain a list of who (plant) i does the exam arocess the best. This j should probab y be broken down to each l portion of the examination. Provide your

( ratings to the utilities in Region 2, so we j can meet your expectations and improve.

5. The arinciaal and t1e utility representative shou d rneet ear y to establis, a workinc relationslia and exaectations. If 30ssible this should inc ude samales of questions, JPMs, etc.

6. The exam should have no outstanding issues /c uestions that arise and neec repair at the last minute. These issues should all have been identified by the arep '

week, to allow time ':o make changes t1at meet al t1e criteria.

7. The chief examiner should explain up

. front all the forms in 1021 tlat need to be.

com aleted. ;

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8. Always check on badging prior to coming on site.

9. As soon as a Chief Examiner is assigned to an exam, the Facility Rep and the Chief shou'd verify the ability to communicate via all clannels (inc uding e-mai). W1en we converted to Lotus Notes, the faci ity was sudden y unable to send e-mail to his Chief Examiner. This

became somewhat of a hindrance anc shou d be avoided if aossible.

10. It would be helpful if the Chief Examiner could arovide lis schedule to t1e Facility Rep. This includes providing u3 dates for 1 any changes to the Chief Examiner's schedule along the way. The facility re3 ;

needs to be aware of when the Chief l Examiner is available to assist in exam preparation activities.

11. A face-to-face meeting should be promptly scheduled in order for the Chief to communicate his exaectations to the Faciity Rep. The face-to-face rec uirement cou d be waived if the Chief and the Faciity Rea lave previously wor <ed together and the Facility Rea is confident that he/she understands t1e Chief's exaectations. In any case, a

[.

t l conference ca would be the minimum to l satisfy this important first ste 3. l

12. The Chief and the Facility Rep should ;

l vvork togetler to establish a firm schedule j for the exam week (s). This will ensure the l most efficient schedule is developed (with l respect to crew composition and

} personnel movement) to minimize the l amount of exam material required.

! 13. The Chief Examiner and Utility Rep MUST l remain fixed during the entire 180 day j period. Handing off the responsibility is j both disru ative and destructive to l communication. The expectation.s of the i

chief examiner must be defined / communicated early.

.14. T1e " time ine" must be enhanced to identify saecific times and dates for communication / working meetings between

1-l the examiner and the utility rep. T1ese j meetings should be " face to face" to

) assure expectations are understood, anc l being met, early on. ,

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l 15. If an examiner and a utiity rep have not

! worked togetler before, the timeline for j " deliverables" must be expanded.

[ Working meetings (face to face) must be i

established for the examiner to review l 5-10 questions,1 scenario,1 jpm,5 jpm l knowledge questions,5 admin questions, j etc. to assure that the standards and j expectations are clear early in the process

! and that tie utiity can aroduce a product i tlat meets the exaectation.

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16. 398 and 396 forms need to be available ;

electronically. We took the time to i develop'an electronic version ourse ves l but I woulc pre"er that the electronic master coales came directly from the NRC

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! so tlat we lave more confidence tlat l everythinc is exactly t1e same. We wou c all benefit from this im arovement.

i l 17. =A face to face working meeting of eight (8)

! to twelve (12) hours, a aproximately two e (2) weeks before the thirty (30? day ;

i submittal must be established to resolve

[ any issues BEFORE the submittal. The j exam materials should be reviewed, line l l by line, at this meeting to communicate all l l changes necessary.

18. Expectations must be estab ished early so tlat t1e utility c ear y understands the ru es and the examiners exaectations. Smal samales of develoament must be reviewed ear y to assure exaectations are being met.

A face to face meeting, arior to the 30 day submittal, to reso ve any/all issues must be scledu ec' such that adec uate time (suggest 2 weeks) is available to resolve

comments before the 30 day limit. l\o one wants to see 30 c uestions reviewed anc the exam rejected. S3ending ~24 hours in 3-4 face to face meetings is a small/ smart price to pay to avoic hundreds of hours of re-develoament, the emotional stress on candidates when the exam must be rescheduled and the impact on the plant l when candidates are not licensed to meet '

plant needs.

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19. The "new" SSNTA format for JPM level of detail is NOT what you have liked in the past and needs to be either accepted by t7e NRC as a standard or oatimum format, or modified, or rejected. The JPMs we su amitted to you were in the "ormat and evel of detail you had found acceptable in tie 3ast, and we were surarised to find that t1ey needed sic nificant last-minute rework (additional eve of detail).

0 1

i 20. Maybe Chief Examiners coulc senc some l coales of good written c uestions, JPMs, i anc JPM questions ua front that cou d hela

! a new ceveloper survive t1e exam writing process and see w1ere you as an

! examiner are coming from.

Facility General Comments

! 1. The limited number of NRC icense l

examiners auts the Region and the sites at a disadvantage with res3ect to getting timely interchange. If the examiner is out of the office on a trip for several weeks, the .

time you have to provide the licensee with feedback is very limited and results in a real struggle to ensure a quality exam.

T1e limited resources and interaction time increases the risk of lower quality.

2. Region 11 examiners have been very 3 rom at in getting back to us when we have a c uestion even though you may be at a remote location.

3. T1e qua ity of t1e communications has been good. All of t1e examiners that I have ta <ed to have been thorough, arecise and have aerformed listening clecks to

! verify t,at the correct messages were sent l and received. I would however, ike to see j more communications by e-mail where l aaproariate. That would he p ensure the l clarity of the communications even more.

! 4. With respect to the exam specifically; there

! were a number of changes that were made l and we had to transmit those by expensive

overnight or next day de ivery. If we could l figure out a secure e-mail method it would l save all of us numerous headaches as well l l as dollars. !

I5.

Durinc my first face-to-face meeting with the Chief Examiner (to review draft exam l material), I gained much-needed insight

! into lis exaectations. T1is alleviated much l stress on my part and, from then on, the

3rocess went muc1 more smoothly. The

Chie" was very le pfu during suasequent j teleahone conversations and our second

i meeting in Atlanta. He was very easy to ,

wor < with and very understanding concerning my inex 3erience in this process. His patient guidance was t1e key

-to our success in this endeavor. Next time, with all we've learned, we'll do even better.

6. The biggest problem that I encountered during that exam came from the written portion that was being developed by the ;

contractor. Since he had written exams before, I assumed that the quality of c uestions he was submitting to us were the c ua ity of questions that were acceptable to the NRC. We reviewed his work, made technica corrections and assumed tlat the cuestions would be acceatec by the NRC.

I had very little communication with the NRC on t1e subject of the written exam and a great deal of communication on the suaject of the operating exam. W1en the submittal was finally made, the focus went

l-l l to tae written exam anc most of the

! communication was made over spea<er

! phones (aaout 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months ). It became a very l painful process and could have been j avoiced lad I not out so muc, fait, in the l contractor's exam writing exaerience and l communicated more on the subject of the l written exam with the chief. We had a

! 100% pass rate on the exam, but the exam

! report was brutal in the area of the written !

j exam.

j 7. Know the chief examiners expectations

! from the beginning (prior to any

! develoament).

8. Never assume you know what you're coing

- the chief is just a ahone cal away.

9. It's better to de iver material and review it in person ratler than over t7e phone. I alan for four or five trips between the start of

l j development anc prep week. It may sound i<e over<i , aut it works ( t's also safer in the area of security).

l 10.' Submit material early (esaecially the written). I ike to have tie written exam a done dea prior to the actual su amittal date.

11. You can never talk to the Chief Examiner too much During the arocess, I talk to him more the i I talk to my mother. l

12. The bottom line is that frequent communication, persona contact, and

'early su amittal of materials is t1e key to a !

successfu NRC exam.

13. ALL 3 rob ems / changes must be resolved at the level of the examiner and the utility re 3. In no case slou d aroblems/clanges be reported /esca ated to senior management of the utility or NRC unless

L l both the examiner and the utility rea are at l an abso ute, and mutually ac reed, l impasse.

l 14. We often felt that we were working in the j dark, writing questions on topics you may

[ not want (as we were waiting for comment j on our skyscrapers), possibly wasting j resources, but seeing no other oation to j meet our required casi-in-stone deadlines.

c

! 15. It's difficult to keea JPMs short and l plausible at the same time.

l 16. W1at is a good " admin JPM", especially for F ROs?

d quesuun: w 1The unit is operating at 20% power with all systems in automatic Bank 'D' control rods are at 120 steps. Control Bank 'C' rod H6 drops to the bottom of the core. No rod control urgent failure alarms occur.

Where will thermal power and RCS Tavg stabilize in response to the dropped rod without any operator action?

A- . Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod.

B. Reactor thermal power will be lower than prior to the dropped rod; RCS Tavg will be within l'F of the temperature prior to the dropped rod.

C. Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be within l'F of the temperature prior to the dropped rod. l D. Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be more than 5'F lower than the temperature prior to the dropped rod. .

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. Answer:

C . Reactor thermal power will be the same as prior to the dropped rod; RCS Tavg will be within l'F of the temperature pdor to the dropped rod.

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! + Keterence Page l

SRO Question 10 RO Question 10 SRO Tier / Group lIl RO Tier / Group 112 SRO Importance 3.7 ROImportance 3.2 JOCFR55.43(b) 10CFR55.41 8 Item Addressed Item Addressed EA Number 000003 AKl.0)

EA Statement Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Reason for turbine following reactor on dropped rod event i

SHNPP Objective AOP-LP-3.1-2 RECOGNIZE automatic actions that are associated with AOP-001, Malfunction of Rod Control and Indication Systems References AOP-LP-3.1 AOP-001 AOP-001 Malfunction of Rod Control and Indication Systems SD-104 Rod Control System t

i Question Source New Justification (A) Select if he does not recognize that rods will step out to restore. temperature and power was restored due to the previous decrease in temperature.

(B) Select if he recognizes that rods will step out, but the decreased temperature adds positive reactivity to restore power.

(C) CORRECT - Power will initially decrease du'ito the dropped rod. As power decreases, temperature will decrease. As temperature decreases, positive reactivity is added to restore !

power. Bank D rods in auto will cause rods to step out. Rods !

l stepping out will restore power and temperature to the original

! value.

(D) Select if he recognizes that power was restored due to the l previous decrease in temperature, but does not recognize that rods will step out to restore temperature and 4

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INITIAL EXAMINATIONS QUESTIONS AND ANSWERS

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TRAINING MANAGERS-CONFERENCE NOVEMBER 5,1998 RICK BALDWIN GEORGE HOPPER I

Initial Written Examinations-

Reference:

All written examinations are written IAW ES-401, " Preparation of Site-Specific Written Examinations for Power Reactors." Using ES-401-1, ES-401-2, ES-401-3, ES-401-4, BWR/PWR, RO/SRO EXAMINATION OUTLINES, and ES-401-6 Written Examination Quality Assurance Checkoff Sheet."

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OBJECTIVES ,

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i O BE1 i ER EXAMINATION PRODUCT I

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i 9 LESS NRC/ FACILITY REWORK

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t; 9 SHARED EXPECTATIONS t i i

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____ __ _-_ ___- ____________ -___ - - - _____ _N

i SESSION OBJECTIVE:

To review validity concepts affecting the NRC . .

written examination for the purpose of:

Instructing licensee personnel toward construction of more VALID and CONSISTENT NRC license examinations.

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-t COVERAGE 9 3 Levels of Validity 9 3 Levels of Knowledge O D.iscriminat. ion, Sampl.ing O Psychometrics 5

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VALIDITY

A valid test is one which tests what it intends to test.

in training examinations, testing specific

. skills and knowledge outlined and taught in '

the objectives.

.In licensing examinations, testing specific

skills and knowledge that SHOULD have been outlined in the objectives.

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3 LEVELS OF VALIDITY O Content ~

O Operational 9 Discriminant t

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CONTENT VALIDITY Addresses K/A coverage and sampling plan Coverage.

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OPERATIONAL VALIDITY '

Addresses two aspects:

1. Is the test item important to be known as a part of the operator's job?

2. Does the test item require the candidate to perform a job RELATED . mental or physical operation?

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DISCRIMINANT VALIDITY Addresses:

G The cut score is the performance level that we use for making a pass / fail decision 80 percent.

O The exam must be written at a level of difficulty that intends to discriminate at

the 80 percent level. t O The question, its stem and distractor, inter.p lay, by DESIGN, at least 80 percent of the candidates taking the exam should answer the item correctly. ,

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-l VALIDITY

SUMMARY

1. The exam must be content valid, '

encompassing job safety significance and sampling. .

2. The test item shculd be operationally .

oriented: a expected mental or psychomotor requirement of the job. The items should be written at the comprehension or analysis level vice simple memory. Items that measure problem solving, prediction, analysis which are essential to job performance.

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VALIDITY

SUMMARY

3. The exam must discriminate at a moderate level of difficulty, set by the cut score.

Meaning the test items as written should provide opportunity for at least 80 percent of the candidates taking the test should j answer the item correctly.

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1 3 LEVELS OF KNOWLEDGE-4 Bloom's Taxonomy

9 Analysis, Application, Synthesis O Comprehension 9 Fundamental (simple memory) t 13

4 LEVEL OF KNOWLEDGE ,

O Bloom's Taxonomy, NRC Reference ,

Benchmark to classify levels of knowledge. ,

O Bloom's Taxonomy, a classification scheme that classifies items by depth of mental performance required to answer the items.

O Bloom's Taxonomy, can be applied to written, scenarios or JPM questions.

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LEVELS LEVEL 1 Fundamental, using simple mental processes, recall or recognition of discrete l bits of information.

i i.e. setpo.in ts, definitions, or specific facts. . ,

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LEVEL 2 Comprehension, involves understanding material through relating it to its own parts or other material:

i.e. including rephrasing information in different words, recognizing relationships ,

, including consequences or implications.

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I LEVEL 3 i

Analysis, synthesis, and application testing is more active and product-oriented testing which involves the multi-part mental process of assembling, sorting, or integrating the parts so that the whole, and the sum can be used to: predict and event or outcome, solve a problem or create something new. ,

c i.e. using-knowledge to solve problems.

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j DETERMINANTS OF DISCRIMINATION i

O Level of examination knowledge i

r G Level of examination difficulty O Passing Score 9 Item bank use 18

- - - - _ _ - - - - - - _ _ - - - - - - - - _ _ _ - - - _ - _ - - -l

I NATURE OF EXAMINATIONS AND TESTS e TESTS are samples of PERFORMANCE O Infer overall performance based on a sample 9 Sample must be broad-based to make confident inference 9 Sample must NOT be fully predictable or inferences cannot be made on untested areas.

e items MUST discriminate otherwise it has little or NO value. -

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PSYCHOMETRICS Items may have one or more of the following psychometric errors: .

1. Low level of knowledge (fundamental)

2. Low operational validity (not job related)

3. Low discriminatory validity ( hard or easy)

4. Implausible distractors

5. Confusing language or ambiguous questions

6. Confusing or inappropriate negatives 1

7. Collection of true/ false statements

8. Backwards logic

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006 Emergency Core. Cooling System J JPM 136 Recovery From Safetylnjection 1

.an'd Solid Water Co~nditions .L - ;- % '

l i Question 2:

Given the following plant conditions:

. Unit 2 was operating at 100% power.

The plant experienced a large break LOCA with a failure of the ECCS system.

FR-C.1, " Response to Inadequate Core Cooling," is being implemented, l

Core exit TCs are 720*F and increasing. l At this point FR-C.] directs the crew to depressurize intact steam generators.

a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?

b.) Why is this action taken? I

!. i References Allowed? YES X NO Answer:

)

a'.) To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.

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Reference:

KA: 006G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs.

OPL271C398 pg 12-15 Applicant Response: SAT __UNSAT l 1 i l

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INADEQUATE CORE COOLING FR-C.1 Rev. 8 )

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l l

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NOTE Blocking low steamline pressure Si as soon as pressurizer pressure is less than 1920 psig will prevent an inadvertent MSIV closure and keep the condenser available for steam dump.

. After the low steamline pressure SI signal is blocked, main steamline isolation will occur if the high steam pressure rate is exceeded. -

. S/G depressurization at the maximum rate may cause S/G narrow range levels to drop to less than 10% {25% ADV). This is acceptable and expected for this

.. inadequate core cooling condition.

' 14. DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:

a. WHEN RCS pressure less than 1920 psig, THEN PERFORM the following:

1) BLOCK low steamline pressure St. .7

2) CHECK STEAMLINE PRESS ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT.

, {M-4 A, A4)

b. DUMP steam to condenser b. DUMP steam at maximum rate at maximum rate. USING intact S/G atmospheric relief (s).

IF local control of atmospheric relief (s) is necessary, THEN D!SPATCH personnel to dump steam i USING EA-1-2, Local Control of

'~

S/G PORVs.

(Step continued on next page.)

Page 13 of 19

006 Emergency Core. Cooling System-/ JPM 136 Recovery From Safetylnjection

.atid Sdlid Water Co'nditions '.' ' . H- -

Question 2:

Given the following plant conditions:

Unit 2 was operating at 100% power.

The plant experienced a large break LOCA with a failure of the ECCS system.

FR-C.), " Response to Inadequate Core Cooling,"is being implemented.

Core exit TCs are 720*F and increasing.

At this point FR-C.1 directs the crew to depressurize intact steam generators.

a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators? e b.) Why is this action taken?

References Allowed? YES X NO i

Answer:

a!) To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.

Reference:

KA: 006G4.18 [ 2.7 / 3.6 ] Knowledge of specific bases for EOPs.

OPL271C398 pg 12-15 Applicant Response: SAT __UNSAT

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l l .'026 Contamment Spray System /.JPM.# 57AP Respond to High Contamment L . Pressure 4 Place'RHR'Spmyin Servic'e'!'- ~

1:

Question 2:

. Given the following plant conditions

l Unit I has tripped from 100% power due to a LOCA.

l Containment pressure is 3.0 psid l Transfer of Containment Spray pump suction to the containment sump is being performed in l accordance with ES-l.3, Transfer to RHR Containment Sump.

a.) Why must both CS pumps be placed in PULL-TO Lock while transferring suction to the l containment sump?

b.) What does placing both CS pumps in PULL-TO-Lock prevent?

References Allowed? YES X NO l

Answer:

a.) While shifting to the containment sump, both the RWST and the containment sump suction valves to the CS pumps will be closed at the same time, b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of water.

Reference:

K/A: 026G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs OPL271C024 pg 14-18 CCD NO:1-47W611-72-1, ES-1.3, pages Il-13, OPL271C388 pg 9 Applicant Response: SAT UNSAT i

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License Applicant Administrative Walkthrough Examination--NRC-1 '

Examiner Sheet A.1: ShiftStaffing ' '

~.

Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming

, outage. He had his last physical examination 18 months ago and has had satisfactory perfonnance in the licensed operator requalification training program.

'He is informed that he is needed to join a shift crew in 3 days to fill in for a

. vacationing Unit OATC.

Can the RO fill in for the vacationing RO? Why or why not? w References Allowed? YES _3__ NO -

P Answer: L No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of "under direction" on-shift time.

Reference:

SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT UNSAT l

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.- License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet

' A~.1 : EShift Staffing' Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew m 2 weeks to fill in for a vacationing shift RO. He had a satisfactory physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of a sMA RO.

What additional requirements must be met by the RO before he may fill in for the j . vacationing RO? #

References Allowed? YES _2(_ NO l Answer: The RO must complete an additional 24 (40 - 16) hours of"under direction" on-shift time that must include a plant tour and shift turnover.

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Reference:

. SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4) l Applicant Response: SAT __UNSAT y

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i Given the following conditions:

1. The reactor has experienced a Steam Generator Tube Rupture.

2. All systems responded as expected.

2. The performance of E0P-04 is in progress. '

3. One Steam Generator has been isolated.

4. All RCPs have been stopped.

5. RCS cooldown using natural circulation is in progress.

Which One of the following describes the concern associated with the isolated l

_SG pressure prior to p acing t e hRCS on SDC?

a. The isolated SG pressure would be too low due to excessive cooldown causing RCS water to enter the SG and reducing RCS inventory. ,

b. The . strategy during the performance of E0P-04 is to maintain the affected SG pressure slightly less that RCS pressure to prevent secondary water entering the RCS.

c. Since the RCS cooldown rate was maintained greater than 30deg/hr. the affected loop has not been cooled sufficiently to allow SG depressurization.

d. The affected SG pressure is high due to thermal stratification of the secondary water.

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Reactor Operator Examination

65. . Given the following conditions:

The reactor has experienced a Steam Generator Tube Rupture.

All systems responded as expected.

The performance ofEOP-04 is in progress.

One steam generator has been isolated.

. RCS cooldown using natural circulation is in progress.

. Which ONE of the following describes the concem associated with the affected SG pressure prior to placing the RCS on SDC? -

, a. 'Ihe SG pressure would be too low due to excessive cooldown causing RCS water to enter I.

the SG and reducing RCS inventory.

~

b. The SG pressure would be slightly less than RCS pressure causing water to enter the RCS resulting in a dilution.

c. The SG temperature would be too high to allow for SG depressu:ization.

d. The SG pressure would be too high due to thermal stratification of the secondary water.

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, Which one of the following describes the response of the Unit 1 charging pumps ;

- following receipt of an automatic SIAS signal, coincident with a Loss of Offsite Power? -

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. 6. One charging pump is automatically started on each emergency bus 5 <

minutes after .it is energized by the diesel. I

b. All charging pumps are automatically started immediately after their !

respective bus is energized.

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c. The operator must manually start one charging pump on each emergency bus -1 5 minutes after it is energized by the diesel. -

d. One charging pump is automatically started onto each emergency bus.

l immediately after it is energized by the diesel. -

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19. ' Which ONE of the following describes the response of the Unit-1 charging pumps following receipt of an automatic SIAS signal, coincident with a Loss of Offsite Power? Assume normal ,

electricallineup and all equipment is operable.

a. Only one charging pump is automatically started on each emergency bus 5 minutes after it is energized bythe diesel.

- b. All charging pumps are automatically started immediately aner their respective bus is energized by the diesel.

c. All charging pumps are automatically started 5 minutes after their respective buses are energized by the diesel.

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d. Only one charging pump is automatically started onto each emergency bus immediately after it is energized by the diesel. i 1

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n. ,, 4 ., .. -, .-. ., +-.n - - - --

Charging pumps are running on Unit 1 an SIAS is present. (Assume no operator action)

Which one of the following lists the charging pump response when the BAM tanks L. are emptied?

The charging pumps will:

a. trip on low oil pressure.

l l b. trip on low suction pressure.

c. automatically align to the RWT.

d. "

continue to run and become gas bound.

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- Reactor Operator Eeination

. 2 7.

Charging pumps are running on Unit I and an SIAS is present. (Assume no operator action)

Which ONE of the following lists the charging pump response when the BAM tanks are emptied?

The charging pumps will:

a. ' trip on thermal overload, b.. ' trip on low suction pressure.

( c. automatically align to the RWT.

d.

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continue to run and become gas bound.

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t 4 , a + .- , . . - . - - . ~ . - -. , , , .

Given the following conditions:

' Unit 1 CEDM' fan HVE-21A is in AUTO after START

, Unit 1 CEDM fan HVE-21B is in AUTO after STOP.

, ' Unit 1 CEDM' fan HVE-21A trips on overcurrent.

- Which ONE of the following completely lists the logic that willL start HVE-21B? !

. a. The trip signal from HVE-21A. 5 lb. The' trip. signal from HVE-21A concurrent with a low flow signal. ;

c. A;10wflowsignal.

d. The trip signal from HVE-21A concurrent with a low flow signal and air inlet temperature to the cooling coils-is greater than 100 deg F.

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Reactor Operator Examination r 59. Given the following conditions:

l Unit 1 CEDM fan HVE-21 A is in AUTO after START.

- Unit 1 CEDM fan HVE-21B is in AUTO after STOP. :

Unit 1 CEDM fan HVE-21 A trips on overcurrent.

Which ONE of the following lists the signals required by the logie needed to start HVE-21B?

a. The trip signal from HVE-21 A. _

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b. . The trip signal from HVE-21 A concurrent with a low flow signal.

l c. A low flow signal ;

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d. The tip signal from HVE-21 A concurrent with a low flow signal and air inlet temperature signal to the cooling coils is greater than 100

F.

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13. Given the following plant conditions:

i . Unit 1 was at 73% power

. A reactor trip / safety injection on low steam line pressure occurred 21 minutes ago

. . Average Core Exit TC temperature is 375'F l

. RCS pressure is 225 psig l

. All S/G pressures are DECREASING slowly I . #2 vei #3 S/G levels are 5% NR and DECREASING slowly

. #1 SIG L*velis 6% NR, and INCREASING slowly

. #4 S/G levelis STEADY at 2% NR l

. Total feedwater flow is 340 gpm !

. PZR levelis 37% and INCREASING

. RCS T-cold temperature is 325'F and DECREASING slowly

. Containment pressure i: 5 psid and INCREASING slowly _

At this po nt, which ONE of the fo!!owing Critical Safety Functions is the MOST degraded? i e

a. Heat Sink l

b. Core Cooling I

c. Containment I

d. Pressurized Thermal Shock l Answer A l

t K/A- 000040K101 [4.1/4.4]

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Reference:

E-0, Foldout Page l

Objective: OPL271C395, B.1 Level: Analysis i

Source: 000040K101

( 001 History: Stem and distracters a and d modified (7/7/98)

Note: Provide PTS curve with this question.

Justification:

a. Correct answer because all S/G levels are Jess tnan 10% NR and total feeowater ik w is iess than 440 ppm.

b. Incorrect because RCS temperature is 325'F (core exit T/Cs less tnan 1200*F;

. in:terect because containment pressure is less than 12.0 psi::.

d. Incorrect because RCS temocrature is 325'F (T-::old is greater than 250*F)

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13. Given the following p! ant conditions:

. Unit 1 was at 73% power A reactor trip / safety injection on low steam line prcssure occurred 21 minutes ago

. . Average Core Exit TC temperature is 3MF

- RCS pressure is,22S'psig liSD M

. All S/G pressures are DECREASING slowly

2 and #3 S/G levels are 5% NR and DECREASING slowly

. *1 S/G levelis 6% NR, and INCREASING slowly

. #4 S/G levelis STEADY at 2% NR

. Totalfeedwatepflow is 340 gpm PZR levelisJr7% and INCREASING

. RCS T-cold temperature is 325'F and DECREASING slowly

. Containment pressure is 5 psid and INCREASING slowly At this point, which ONE of the following Critical Safety Functions is the MOST degraded?

a. Heat Sir.k

b. Core Cooling

. Containment

d. Pressurized Thermal Shock l

Answer: A K/A: 000040K101 (4.1/4.4]

Reference:

E-0, Foldout Page Objective: OPL271C395, B.1

?

Level: Analysis ,,

a s

Source: 000040K101 001 History: Stem and distra:ters a and d modified (7T//98)

Note: Provide PTS curve with this question.

Justnization:

l'

a. Cone:t answer because all SIG levels are Jess tnan 10% NR and total feeawater fiow rs less than t-40 gpm.

b. Incorrect becau;,e RCS temperature is 325': (core exit T/Cs less tnan 1200'F).

c. Incorrect oe:ause contninment pressure is less tnan 12.0 ps:d.

d. Incorrect because RCS temoerature is 325': (T-5oid is greater tnan 250*:)

r ,

/./

~;. .,& , .i , % e %W, n M: ""* 5

.h% u-% ' a.c n - % W "- T 1 -

9

' j',c.y- k J 94-6

.C i .

.l(, l,,t/ ,C aan }h2 *M -

4n . i h=a

4

20. Given the following plant conditions:

. The control room has been evacuated due to a fire

. All controls have been transferred per AOP-C.04

- . MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators

. The TDAFW pump has been shut down t-

. Steam generator pressures and levels are decreasing Which ONE of the following describes the response of the auxiliary feedwater system?

a. The TDAFW pump will automatically restart when 2/4 steam generators reach low low level.

b. The MDAFW pump level control valves will automatically control steam generatof ~

levels at 33%.

c. The MDAFW pump level control valves will have to be manually adjusted using the Manual Output Adjust in the L-381 cabir.et.

d. The discharge pressure for the MDAFW pumps will have to be manually adjusted by throttling the manual valves at the LCVs.

Answer: B K/A- 0000SSA102 (4.3 / 4.5) ,

Reference:

AOP-C.04, page 11 Objective: OPL271C423. B.4 Level: Comprehension Source: 00006SA102 001 History: Used on 9/97 RO NRC exam Text modified to correct grammar errors. Distracters a, b, c, and d reordered (7/22/98). Distracter be restructured (7/29/98)

Note: Selected from@ exam bank with minor modification of text b

w

, - - - N-

20. Given the following plant conditions:

. The control room has been evacuated due to a fire

. All controls have been transferred per AOP-C.04

- . MDAFW pumps 1 A-A and 1B-B are injecting into the steam generators

. The TDAFW pump has been shut down ,

. Steam generator pressures and levels are decreasing

,c.be sco J s-

, % 4 k w&W M MF-C.ON Which ONE of the followhg describes the recpens; v: um od.my lesd, vater-system?

~

a. The TDAFW pump will automatically restart whan 2/4 steam generators reach low low level e ~ $+ k ~* A Oob # U4'My ft V38/ ,

(8lc a

b. The MDAFW pump level control valves will automatically control steam generator , I

, levels at 33%.

The MDAFW pump level control valves will have to be manually adjusted using the Manual Output Adjust in the L-381 cabinet.

tW

,~~Y,gg

/ y

. d. The discharge pressure fer the MDAFW pumps will have to be manually adjusted by tnrottling the manual valves at the LCVs.

j/ot p'j. Answer B l K/A: 000058A102 [4.3 / 4.5]

Reference:

AOP-C.04, page 11 Objective: OPL271C423. B.4 L= vel: Comprehension Source: M 00005BA102 001 H: story: Used c,n 957 RO NRC exam ,

Text modified to correct grammar errors. Distracters a, b, c. and d reordered j (7/22/98). Distracter be restructured (7/29/98)

Note: Selected fromMexam bank with minor modification of text l

i I

i 4

1

. \

a

23. Given the following plant conditions:

. FR-C.1,

inadequate Core Cooling", has been entered due to a RED path on Core Cooling

. Core exit temperatures (TCs) are 1250*F and increasing

. NO Feedwater / Aux Feedwater is available

. At step 12, the CRO checks the S/G NR levels and reports all are <10%.

As the SRO you should: (Select ONE of the following)

a. Go to FR-H.1,

Loss of Secondary Heat Sink *,

b. Depressurize allintact S/Gs to atmospheric pressure to dump accumulators.

c. Start FCPs one at a time, until core exit TCs are less than 1200'F.

4

d. Prepare to initiate RCS Feed and Bieed if WR level in any 2 S/Gs is less than 60%.

Answer: C K/A: 000074K307 . [4.0/4.4]

Reference:

FR-C.1, pages 10 & 17 Objective: OPL271C398 Level: Comprehension Source: MExam Bank 101. 000074K307 001 History: Used on HLC 9807 practice exam Distracters b and c reordered Note: Selected froMexam blink without modification of text I

1 l

l 1

1 l

l l

.:.. g INADEQUATE CORE COOLING FR-C.1

[ Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED n

CAUTION Use of a Fautted or Ruptured S/G during performance of the following steps may compound the emergency shuation. When NO frrtact S/Gs are available, a Fautted or Ruptured S/G may be used. '

i

12. MAINTAIN Intact S/G narrow range :

leveis:

! a. Greaterthan 10% [25% ADV) a. MAINTAIN total feed flow greater than 440 gpm UNTil level greater than 10% [25% ADV)

in at least one S/G.

IF total feed flow greater than 440 gpm can NOT be established,

' THEN PERFORM theiollowing:

1) CONTINUE attempts to establish heat

sink in at least one S/G.

,, 2) GO TO Note prior to Step 21.

ir-

b. Between 10% [25% ADV) and 50%.

o*

Page 10 of 19

- = _ . . - . _ - . - - -- . -

FR-C.1

+

g INADEQUATE CORE COOLING Rev. 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

... J J

NOTE RCP damage due to absence or loss of norrnal support conditions is an acceptable consequence in this procedure.

l

21. CHECK if RCPs should be started:

a. , CHECK core exit T/Cs a. GO TO Step 22.

greater than 1200*F.

b. CHECK ifidle RCS loop available: b. PERFORM the following:

1) S/G narrow range level a) OPEN pressurizer PORVs and block greater than 10% {25% ADV) valves.

2) RCP in associated loop b) IF core exit T/cs remain AVAILABLE AND STOPPED. greater than 1200*F, THEN OPEN reactor vessel head vents:

. FSV-66-394

- FSV-68-395

. FSV-68-396

. FSV-68-397.

c) GO TO Step 22.

c. START RCP in one idle loop.

d. GO TO Substep 21.a.

Page 17 of 19

^

\

l l

l

23. Given tne following plant conditions:

. FR-C.1, Inade:;uate Core Cooling'. has been entered due to a RED path on Core Cooling

,. . Core exit temperatures (TCs) are 1250*F and increasing i

. NO Feedwater / Aux Feeowater is available

. At step 12, the CRO checks the S/G NR ievels and reports a!! are <10% l As the SRO you should: (Select ONE of the following)

a. Go to FR-H.1,

Loss of Secondary Heat Sink".

b. Depressurize allintact S/Gs to atmospheric pressure to dump accumulators,

c. Start RCPs one at a time, until core exit TCs are less than 1200*F. 3 M POR\ls are 3 L oc.N \/M.w.5

d. _Erepass404aitiaMOSferJ mJGeed4WRieveHerany2-S/Gs-is4ess-than-50%

Answer: C, K/A: 000074K307 [4.0/4.4]

Reference:

FR-C.1, pages 10 & 17 Objective: OPL271C52C Level: Comprehension Source: 000074K307 001 History: Used on HLC 9607 practice exam Distracters b and c reordered Note: Selected fromMexam bank without modification of text p.p h /W6!U Y j i

J

49. Given the following plant conditions:

. Reactor power is at 20% during a unit shutdown

. Interrnediate Range N-36 failed high

. Operators placed the level trip bypass switch for N 35 to the bypass position Which ONE of the following describes the effect of this failure and action during the remainder of the shutdown?

a. The reactor will automatically trip when the Power Range channels decrease below the F-10 setpoint.

. b. Entry from Mode 1 to Mode 2 is prohibited with an inoperable intermediate Range chanrul, so the unit must be manually tripped prior to Mode 2 entry.

c. .Both Source Range channels, N-31 and N-32, must be manually energized when the operable intermediate Range channel (N-35) decreases below the P-6 setpoint.

d. Source Range channel N42 must be manually energized when the operable intermediate Range channel (N-35) oecreases below the P-6 setpoint; Source Range channel N-31 will automatically energize.

Answer- C K/A: 015000K407 [3.7/3.8)

Reference:

AOP-l.01, page 10 ES-0.1, page 13 Objective: OPL271C352, B.4 Level: Comprehension Source: 015000K407 001 History: Not used ore 9/97 or 5/98 NRC exams. Not used on practice exam.

Distracters e and d reordered Note: Selected fromg exam bank without modification of text l

W

&$ g,j ,4 C& ,fW

/ /

Given the following plant condriions:

3[ , I /' N.

49. ,,

. Reactor power is at 20% during a unit shutdown ts

. intermediate Range N-36 failed high j

," Opera orsrpfaM m :: ';mp eypass-sw:terrior#3Mo the DypaMkidh l s

Which ONE of the fo!!owing describes the effect of this failure and action during the remainder of i the shutdown?

l

a. The reac:or will automatically trip when the Power Range channels decrease below '

. the P-10 setpoint.

b. Entry from Mode 1 to Mode 2 is prohibited with an inoperable Intermediate Range channel, so the unit must be manually tripped prior to Mode 2 entry.

c. -Both Source Range channels, N-31 and N 32, must be manually energized when the operable Intermediate Range channel (N-35) decreases below the P-6 setpoint.

d. Source Range channel N-32 must be manually energized when the operable l intermediate Range channel (N-35) decreases below the P-6 setpoint; Source Range 1 channel N-31 will automatically energize.

l Answer. C l

ll \

K/A: 015000K407 [3.7/3.8) l Reference; AOP-LO1, page 10 ES-0.1, page 13 Objective: OPL271C352 B.4 Level: Comprehension Source: 015000K407 001 l History- Not used on 9/97 or 5/98 NRC exams. Not used on practice exam.

h Distra:ters c and d reorcered 3

I\ Note: Selected fromMexam bank without modification of text

\

l s

.k,c<l ' d >~aD-a/(gn i d' u w' 5 w/

. i m

, l

I i

)

' 35. Given the following plant conditions:

I

. . Unit 2 is operating at 29% power in accordance with 0-GO-6, Power Reduction From 30% Reactor Power to Hot Standby

'.- . Unit 2 will be goini, to Cold Shutdown for rnaintenance

. intermediate Range N-36 has just failed high Which ONE of the following r.ctions must be performed before reducing reactor power below 10%?' ,

. a. Manually energize N-31 and N-32.

b. Place N-36 LevelTrip switch in BYPASS.

c. Remove N-36 instrument power fuses. e

d. Manually trip the reactor to prevent an automatic reactor trip.

Answer: B K/A: 000033K302 [3.6/3.9)

Reference:

AOP-l.01, page 10 & 13 t

Objective: OPL271C352, B.4 Levet: Analysis Source: New question (Developed 7/15/98) .

Justification:

a. Incorrect because manually restoring N-31 and N-32 to operation in the power range would i destroy the source rarige detectors,

b. Correct because placiag the level trip switch in BYPASS prevents high reactor trip when l

. the low power reactor trip signal is reinstated at the r -10 setpoint (10% power). l

c. Incorrect because action does not bypass the trip signal.

d. Incorrect because a manual reactor trip for the given condnions is not reouired. Placing N-3S level trip swnch in BYPASS allows an orderly reactor shutdown.

i 1

a i

I

)

50. Given the following plant conditions:

. Large Break LOCA is in progress

. RCS pressure is 550 psig

- . Exosensor indicates 25'F superheat ,

. No RCPs are operating Which ONE of the following indications would the operator use along with RCS pressure to 1

accurately substantiate core cooling? ;

a. Reactor Coolant Tavg value. I

b. Average value of all core exit thermocoupies. l l

c. Hottest Reactor Coolant wide range Thot value.

d. Average value of five hottest core exit thermocouple:.

1 Answer. D I l

K/A 017000A402 [3.8 / 4.1]

Reference:

FR-0, page 3

)

OPL271C044, page 7. A.1.c l Objective: OPL271 C044, B.1.b )

Level: Memory i Source: 017000A402 001 History: Used on HLC 9809 practice exam l Distracters a, b, c, and d reordered (7/22/98) .

Note: Selected fr m xam bank without modification of text

J e l s

l

50. Given tne following plant condnions.

- Large Break LOCA is in progress

- RCS pressure is 550 psig

- Exosensor indicates 25'F superheat !

- No RCPs are operating Which ONE of the following indications would the operator use along with RCS pressure to accurately substantiate core cooling?; j, , , , ,,

l w.. - - _ _ . - _.

_ , a ,

n

/ >

'aT~ Read:iC00;60;i6hN!$N'fA~4 _ &, , y,,,) W/9*' ' ' *

< n e we w ; .

b. Average value of all core exit thermocouples.

c Hottest Reactor Coolant wide range That value. -

d. Average value of five hottest core exit thermocouples.

Answer: D .,

K/A 017000A402

,5 p,b' o#wMc &&

[3.8 / 4.1]

~

Beference: FR-0, page 3 OPL271 C044, page 7 A.1.c Objective: O?L271 C044, B.1.b Level: Memory Source: 017000A402 001 History: Used on HLC 9809 practP,e exam Distracters a, b, c, and ri reordered (7/22/98)

Note: Selected rom exam bank without modification of text

d i

v" g

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2 O M

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l w w w a

08 og z $a 2g

< zo < e '

er <w c a i er oz< l l c5 c< g<> >

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en se < m OW$am 4 C

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w m o -

1 =

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l O T O ab Wo H ," e

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-- ~ .o ep5 OE zEWP w [E 2 CC.m i jOwOa wC at J 'o,

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W" = r=

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r., x Dy=d m ,W== g <C 5 <' "Ow W- '

O s<s.. ~ ~ .- mm$w<

g w :" w*-= w m G o w *- D -[. m U<OC g gm CmMJN m 30 0-w COUU m 2 .- = <CaOxO 6.,w -62 Eg$ .. -mw =-Oc-

] f 52'O-i m W '

- cowc m BOO <pt O w 6 C O LO

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4

88. Given the following plant conditions:

. Unit 2 operating in accordance with 0-GO-5, Normal Power Operation at 73% with a power increase to 100% in progress

. . Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm

. Current time is 0100 Which ONE of the following actions must be taken?

a. Immediately stop the power increase.

- b. Continue the power increase while restoring loop 1 accumulator boron concentration to 2400 to 2700 ppm boron within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

c. If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in HOT:

< STANDBY by 0700.

d. If loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , reduce pressurizer pressure to 1000 psig or less by 1300.

Answer: A K/A: 2.1.1 [3.7/3.8)

Reference:

SSP-12.1, Page 31 Objective: OPL271C209, B.2 Level: Comprehension Source: . New question (Developed 7/20/98) -

Note: Provide copy of Technical Specification 3.5.1.1 with the question (exam) 4 Justification: i e

a. Correct becausegConduct of Operation (SSP 12.1) restricts power increase when in an LCO action of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or less. RCS loop 1 accumulator boron concentration cf 2390 ppm boron places Unit 1 in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO.

b. Incorrect because power increase is not allowed when in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO action statement.

c. Incorrect because if loop 1 boron concentraticn is not restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Unit 1 must be in HOT standoy by 0800.

d. Incorrect because if loop 1 boron concentration not restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , pressurizer pressure must be reduced to 1000 osig or less by 1400.

l 1

j l

l

. I

4 3 /4.5 ENERGENCY CORE COOLING SYSTEMS 3 /4. 5.1 ACCUMU,A_Tj,PJ f

COLD LEG INJEC110N ACCUMULATORS LIMITING CONDITION FpR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:

a. The isolation valve open, g131

b. A contained borated water volume of between 7615 and 8094 gallons of .

borated water, r

. c. Between 2400 and 2700 ppra of boron,

d. A nitrogen cover-pressure of batween 600 and 683 psig, and R184

e. Power removed from isolation valve when RCS pressure is above 2000 psig.

APPLICABILITY: MODES J , 2 and 3.*

ACTION:

a. With one cold leg injection accumulator inoperable, except as a result of boron concentration not within limits, restore the inoperable accumulator to OPERABLE status within one hour or be in at least HDT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to 1000 psig or less within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one cold leg injection accumulator inoperable due to the baron concentration not within limits, restore boron concentration to withinil.mitsowithin i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to 1000 psig or less within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . -

Pressurizer pressure above 1000 psig.

De:c:ber 27, 1994 Amendment No. 113, 131, 133,

- UNIT 2 3/4 5-1 141, 154

.) ,) f. ' .S Yrl } h/'

68. Given the following p! ant conditions:

. Unit 2 operating in a:Cordance with 0-GO 5, Normal Power Operation at 73% with a powerincrease to 100% in progress

<- /,g . Chemistry reports Unit 2 RCS loop 1 accumulator boron concentration is 2390 ppm

,p M > Current time is 0100 4 /

Which ONE of the fotfowing actions must be taken?

a. Immediately stop the power increase. ,

b. Continue the power increase while restoring loop .1 accumulator boron concentration to 2400 to 2700 ppm boron.J-J .1 heen h&WW 72. kou Cf.

c. 11 loop 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in HOT

STANDBY by 0700,

d. If loco 1 accumulator boron concentration is NOT restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , reduce pressurizer pressure to 1000 psig or less by 1300.

Answer: A K/A: 2.1.1 {3.7/3.8]

Reference:

SSP-12.1, Page 31 Objective: OPL271C209, B.2 Level: Comprehension Source: New question (Developed 7/20/98)

Note: Provide copy of Techni:al Specifi:ation 3.5.1.1 wnh the question (exam)

/

Justification:

a, Correct becaus ondu:t of Operation (SSP.12.1) restri:ts power increase when in an LCO acuan ot o nours or less. RCS loop 1 a::umulator coron concentrat on of 2390 ppm boron places Unit 1 in a 1 hout LCO.

b. Incorrect be:ause power increase is not allowed wnen in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO action statement.

c. incorrect because if loop 1 boron concentration is not restored witnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Unit 1 I must be in HOT standby by 0B00.

, d. in:orre:1 because if loop 1 boron concentration not restored wnnin 1 nour, oressurizer pressure must ce reduced to 1000 psig or less by 1400.

t

// , _, s i / /.-

w'

/c

l: ll j)L . A <

pp -@* -

7 , ,_ ,, Y

,Cj) n' f'/T.

ml e n 3

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. l

s:

006 Emergency Core Cooling System Q JPM 136 Recovery From Safetylnjection

.and Sdlid Water Co~nditions'. .J- . ;N Question 2:

Given the following plant conditions:

Unit 2 was operating at 100% power.

The plant experienced a large break LOCA with a failure of the ECCS system.

FR-C.1, " Response to Inadequate Core Cooling," is being implemented.

Core exit TCs are 720'F and increasing.

At this point FR-C.1 directs the crew to depressurize intact steam generators.

a.) What is the basis for the direction in FR-C.1 to depressurize intact steam generators?

b.) Why is this action taken?

References Allowed? YES X NO Answer:

a.) To reduce RCS pressure below 125 psig b.) To allow the ECCS accumulators and RHR pumps to inject water to the RCS.

Reference:

KA: 006G4.18 { 2.7 / 3.6 ] Knowledge of specific bases for EOPs.

OPL271C398 pg 12-15 Applicant Response: SAT UNSAT l

l

{-

l l -

i h

L i

FR-C.1

' ' INADEQUATE CORE COOLING Rev. 8 l -. I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

~~

NOTE . Blocking low steamline pressure Si as soon as pressurizer pressure is less than 1920 psig will prevent an inadvertent MSIV closure and keep the condenser available for steam dump.

. After the low steamline pressure SI signal is blocked, main stes.mline isolation will occur if the high steam pressure rate is exceeded. :

. S/G depressurization at the maximum rate may cause S/G narrow range levels to

~

drop to less than 10% [25% ADV). This is acceptable and expected for this inadequate core cooling condition.

l

14. DEPRESSURIZE Intact S/Gs to reduce RCS pressure to less than 125 psig:

a. WHEN RCS pressure less than 1920 psig, THEN PERFORM the following:

l- 1) BLOCK low steamline pressure I

St. ::

l 2) CHECK STEAMLINE PRESS

! ISOUSl BLOCK RATE ISOL ENABLE permissive LIT.

l [M-4 A, A4) l i

b. DUMP steam to condenser b. DUMP steam at maximum rate l USING intact S/G atmospheric relief (s).

!- at maximum rate.

IF local control of atmospheric relief (s) is necessary, THEN DISPATCH personnel to dumo steam USING EA-1-2, Local Control of S/G PORVs.

(Step continued on next page )

M Page 13 of 19

\

l 026 Conrainment Spray System /,JPM # 37AP Respond to High Contamment

~

Pressti$0Phice'RHR Sp' ray.iil SeiviceN: #

(

Question 2:

Given the following plant conditions:

Unit I has tripped from 100% power due to a LOCA.

Containment pressure is 3.0 psid Transfer of Containment Spray pump suction to the containment sump is being performed in accordance with ES-1.3, Transfer to RHR Containment Sump. ,

1 l

a.) Why must both CS pumps be placed in PULL-TO: Lock while transferring suction to the l

containment sump? I b.) What does placing both CS pumps in PULL-TO-Lock prevent?

l References Allowed? YES X NO

! Answer:

a.) While shifting to the containment sump, both the RWST and the containment sump suction !

valves to the CS pumps will be closed at the same time. l l b.) Placing the CS pumps in PULL-TO-Lock will prevent running a CS pump without a source of l water.

Reference:

YJA: 026G4.18 [ 2.7 / 3.6 ) Knowledge of specific bases for EOPs OPL271C024 pg 14-18, CCD NO:1-47W611-72-1. ES-1.3, pages Il-13, OPL271C388 pg 9 Applicant Response: SAT UNSAT__

4 1

License Applicant Administrative Walkthrough Examination--NRC-1 '*

Examiner Sheet A'.1:? Shift Staffing ' -

~~

Question 1: A licensed RO has been off-shift for 6 months to assist in scheduling an upcoming outage. He had his last physical examination 18 months ago and has had satisfactory performance in the licensed operator requalification training program.

He is informed that he is needed to join a shift crew in 3 days to fill in for a -

vacationing Unit OATC.

,. Can the RO fill in for the vacationing RO? Why or why not? w References Allowed? YES 2f NO -

Answer: No. The RO must first reactivate his license by completing at least 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of '

"under direction" on-shift time.

Reference:

SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT U SAT I

Y l

E 4

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,c' License Applicant Administrative Walkthrough Examination--NRC-1 Examiner Sheet A'.1:1 Shift Staffing 3 Question 1: A licensed RO has been off-shift for 6 months to assist in outage scheduling. He is informed that he is needed to join a shift crew in 2 weeks to fill in for a vacationing shift RO. He had a satisfactoy physical examination 18 months ago and has maintained satisfactory performance in the licensed operator requalification training program. In anticipation of rejoining a shift crew, the RO has spent two 8-hour shifts in the control room as the OATC during the past month under the direction of a shift RO..

What additional requirements must be met by the RO before he may fill in for the vacationing RO? r References Allowed? YES1NO Answer: The RO inust complete an additional 24 (40 - 16) hours of"under direction" on-shift time that rnust include a plant tour and shift turnover.

Reference:

SSP-12.1, Conduct of Operations, p. 61 and 62 K/A 2.1.4 (2.3/3.4)

Applicant Response: SAT UNSAT y

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ML20199E388

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ML20199E388

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